US4655994A - Method for determining the operability of a source range detector - Google Patents

Method for determining the operability of a source range detector Download PDF

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Publication number
US4655994A
US4655994A US06/567,447 US56744783A US4655994A US 4655994 A US4655994 A US 4655994A US 56744783 A US56744783 A US 56744783A US 4655994 A US4655994 A US 4655994A
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detector
voltage
electrodes
source range
reactor
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US06/567,447
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English (en)
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Lesley Greenberg
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Westinghouse Electric Co LLC
CBS Corp
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Westinghouse Electric Corp
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Assigned to WESTINGHOUSE ELECTRIC CORPORATION reassignment WESTINGHOUSE ELECTRIC CORPORATION ASSIGNMENT OF ASSIGNORS INTEREST. Assignors: GREENBERG, LESLEY
Priority to US06/567,447 priority Critical patent/US4655994A/en
Priority to EP84309018A priority patent/EP0147212B1/de
Priority to DE8484309018T priority patent/DE3478366D1/de
Priority to ES539064A priority patent/ES8702058A1/es
Priority to JP59275030A priority patent/JPS60158390A/ja
Priority to KR1019840008595A priority patent/KR850004696A/ko
Publication of US4655994A publication Critical patent/US4655994A/en
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Assigned to WESTINGHOUSE ELECTRIC CO. LLC reassignment WESTINGHOUSE ELECTRIC CO. LLC ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: CBS CORPORATION (FORMERLY KNOWN AS WESTINGHOUSE ELECTRIC CORPORATION
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/108—Measuring reactor flux
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a method for determining the operability of a source range detector disposed in the vicinity of an operating nuclear reactor.
  • it provides a method of determining the operability of a source range detector, without damaging the detector, while the reactor is operating in the intermediate or power range.
  • the power level of a nuclear reactor is generally divided into three ranges: the source or start-up range, the intermediate range and the power range.
  • the power level of the reactor is continuously monitored to assure safe control and operation. Such monitoring is conducted by means of neutron detectors placed outside but adjacent to the reactor core for measuring the neutron flux of the reactor. Since the neutron flux at any point in the reactor is proportional to the fission rate, the neutron flux is also proportional to the power level of the reactor.
  • Fission and ionization chambers have been used to measure neutron flux in the intermediate and power range of a reactor. Such fission and ionization chambers are capable of operation at all normal reactor power levels without damage; however, they are generally not sensitive enough to accurately detect the low level neutron flux emitted in the source range. Thus, separate low level or source range detectors are used to monitor neutron flux when the power level of the reactor is in the source range.
  • proportional counters As disclosed in U.S. Pat. No. 4,186,048, it is known to use proportional counters as source range detectors because they are extremely sensitive and hence highly suitable to detect the low energy radiation produced by a nuclear reactor in its start-up range.
  • a typical proportional counter used for such purposes is a Type WL-23706 boron trifluoride (BF 3 ) gas-filled proportional counter made by Westinghouse Electric Corporation.
  • BF 3 boron trifluoride
  • Such a proportional counter has an electrode structure which includes a fine central wire which acts as the anode and an annular cathode which surrounds the anode.
  • incident neutron radiation will liberate electrons from gas atoms within the counter to create electron-ion pairs.
  • a high electric field is produced between the electrodes of the device by applying a corresponding high voltage across the electrodes.
  • gas multiplication or avalanche gain occurs in the high field region surrounding the wire anode whereby the initial electrons liberated by neutrons collide with other gas atoms to create additional electron-ion pairs in the gas.
  • the resulting charge is swept out of the gas by the electric field, the electrons moving to the anode, and positive ions moving to the cathode.
  • the moving charge causes a current to flow in an external circuit.
  • a novel method for determining the operability of a source range detector located adjacent a nuclear reactor including the steps of: (a) operating the reactor at a power level above the source range; (b) applying a voltage across the electrodes of the detector, the voltage having a magnitude below that necessary to generate a neutron count from the detector; (c) gradually increasing the magnitude of the voltage across the electrodes of the detector until the detector just begins to generate a neutron count; (d) reducing the voltage across the electrodes of the detector; and (e) replacing the detector if a neutron count is not generated in step (c) at a voltage having a magnitude less than a predetermined voltage magnitude.
  • a significant advantage of the method according to the invention is that it permits checking the source range detector during normal operation of the nuclear reactor and allows time for a spare detector to be installed in place of a failed detector or for other administrative safeguards to be undertaken.
  • the method may be carried out automatically on a periodic basis to assure operability of the detector.
  • a microprocessor is employed to automatically and periodically adjust the voltage.
  • a calibration is performed early in the life of the detector whereby the voltage at which the detector starts counting neutrons at a given reactor power level above the source range is recorded. Thereafter the voltage at which the detector starts counting neutrons at the same reactor power level is compared to the recorded voltage. The voltage difference if any, corresponds to the degree of deterioration of the detector output.
  • FIG. 1 is a graph showing a typical operating characteristic curve of a BF 3 gas-filled proportional counter.
  • FIG. 2 is a partial block diagram and a partial circuit schematic of an arrangement for implementing the method according to the invention.
  • FIG. 1 shows a typical operating characteristic of a BF 3 gas-filled proportional counter, such as the Westinghouse WL-23706, with which the method according to the invention can be employed.
  • the method of the invention is not however, limited to a BF 3 gas-filled proportional counter, but rather is particularly applicable to any proportional counter having a center wire anode which must be protected against excessive currents while testing for operability at high reactor power levels.
  • a type WL-22791 B 10 lined proportional counter also made by Westinghouse Electric Corporation, is another example of a proportional counter with which the method according to the present invention can be used. Still other types of counters may be used in practicing the invention.
  • the curve shows that as the voltage across the electrodes increases the number of neutron events counted by the detector also increases until the detector is counting all neutron events, at which point the curve flattens out.
  • the useful part of the operating characteristic shown in FIG. 1 is between 1800 and 2000 volts, the latter constituting a typical high voltage setting for source range detection. Depending on the particular BF 3 detector, the useful part of the curve could range between 1500 and 2500 volts.
  • a B 10 lined detector has a similar operating characteristic except that the voltage range of the operating part of the characteristic is generally lower, between 750 and 1500 volts.
  • this counter which is described in greater detail in Westinghouse Technical Data Sheet 86-276T, dated June 1975, has a center wire anode made of tungsten and an 1100 aluminum alloy annular cathode surrounding the wire anode, both of which are disposed in a housing filled with BF 3 gas at a pressure of 55 cm Hg.
  • the WL-23706 counter has a sensitivity of 13 counts/neutron/cm 2 at an operating voltage of 2000 volts and is designed to operate in the presence of a maximum neutron flux of 10 6 nv, where nv is the unit neutron flux in neutrons/cm 2 /sec.
  • the maximum permissible count rate of the WL-23706 is 10 6 counts per second (cps), after which the current generated through the counter is potentially damaging to the electrode structure.
  • a count rate of 10 6 cps corresponds to a flux at the top of the source range, or about 10 -3 percent of maximum reactor power.
  • the WL-23706 is thus not designed to operate at its operating voltage in the presence of neutron flux corresponding reactor power levels above the source range.
  • the WL-23706 proportional counter were energized in the presence of neutron flux corresponding to the intermediate or power range of a nuclear reactor at a voltage of 2000 volts, which is a typical operating voltage in the source range, the number of neutron events within the counter would result in a current through the counter that would melt the center electrode wire of the counter. This of course would render the counter inoperable.
  • the present invention provides for the steps of gradually increasing the voltage across the electrodes of the counter, from an initial voltage magnitude which is well below the level at which the proportional counter will begin to count neutrons, to a magnitude at which the proportional counter just begins to count neutrons, which is indicated by a meter contained in an associated counting channel connected to the proportional counter. Thereafter, the voltage applied to the electrodes is decreased to a safe level (i.e. below the avalanche gain portion of the operating characteristic) so that any current generated by the proportional counter as a result of incident neutron flux would be insufficient to melt the electrodes.
  • a safe level i.e. below the avalanche gain portion of the operating characteristic
  • the voltage is generally reduced to zero since the source range detector is not used in its operational mode at the high reactor power levels.
  • the initial voltage magnitude from which the voltage is gradually increased is likewise generally zero.
  • the initial voltage magnitude could be up to approximately 560 volts, 560 volts being below the avalanche gain portion of the operating characteristic for a BF 3 gas-filled proportional counter and hence below the level which could produce a damaging current through the counter.
  • the initial voltage magnitude could be up to approximately 250 volts.
  • the proportional counter does not generate a count by the time the applied voltage reaches its rated maximum operating voltage, the counter is presumed defective and appropriate administrative safeguards are undertaken, such as replacing or repairing the defective counter.
  • FIG. 2 illustrates a circuit for implementing the method according to the invention.
  • a proportional counter 10 such as the BF 3 gas-filled device described above, having an electrode structure including a center wire for an anode 12 and a cathode 14 surrounding the wire anode 12, is connected at its anode 12 to a preamplifier 16.
  • Cathode 14 is connected to ground.
  • preamplifier 16 includes a decoupling resistor 18 connected at one end to a terminal 20 adapted to be connected to anode 12 of proportional counter 10 and connected at its other end to a terminal 22 which is adapted to receive an input from a controllable high direct voltage source 24.
  • a bleeder resistor 26 and a noise filtering capacitor 28 are connected in parallel between terminal 22 and ground.
  • An amplifier 30 has its input coupled via a D.C. blocking capacitor 32 to terminal 20 and its output to a terminal 34 for passing amplified current pulses produced by counter 10 to a counting channel 36.
  • Counting channel 36 may be implemented by Westinghouse Part No. 6081D50 or any other suitable source range counting equipment. Westinghouse Part No. 6081D50 has an analog voltage output which is calibrated in counts per second.
  • voltage source 24 is initially set to zero or a relatively low voltage so that proportional counter 10 is insufficiently energized to detect neutrons even while the reactor is operating in the intermediate or power range.
  • counting channel 36 is used to detect when a neutron count is first generated by proportional counter 10.
  • the voltage of voltage source 24 is reduced, preferably to zero volts for reasons previously discussed.
  • the method of the invention may also be carried out automatically with the use of a microprocessor 38, such as an Intel 8080.
  • Microprocessor 38 is connected for controlling voltage source 24 automatically on a periodic basis. It is programmed to periodically gradually increase the voltage of the voltage source until a count is first generated by proportional counter 36. If no count is generated by the time voltage source 24 reaches the rated maximum operating voltage for the proportional counter, then microprocessor 38 activates an alarm 40, after which the necessary safeguards are undertaken by attending personnel.
  • the proportional counter As the proportional counter ages, its output will deteriorate. That is, for a given reactor power level, it will take a greater voltage across the electrodes to produce the same neutron count. In accordance with a further feature of the invention, this deterioration can be measured.
  • a calibration is performed, whereby the proportional counter is subjected to a given neutron flux corresponding to a given reactor power level above the source range of the reactor. As before, the voltage is gradually increased until a test voltage is reached at which the counting channel first registers a count indicating that neutrons are being detected by the detector. This test voltage is recorded and the proportional counter is de-energized.
  • the operability of the proportional counter is determined by subjecting the proportional counter to the same given neutron flux (i.e. same given reactor power level) and again noting the voltage level at which the proportional counter first generates a neutron count.
  • the difference, if any, between this latter voltage and the test voltage obtained during the calibration corresponds to the degree of deterioration of the output of the proportional counter.
  • the relative operability of the proportional counter is obtained with reference to a calibration point.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Measurement Of Radiation (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US06/567,447 1983-12-30 1983-12-30 Method for determining the operability of a source range detector Expired - Lifetime US4655994A (en)

Priority Applications (6)

Application Number Priority Date Filing Date Title
US06/567,447 US4655994A (en) 1983-12-30 1983-12-30 Method for determining the operability of a source range detector
EP84309018A EP0147212B1 (de) 1983-12-30 1984-12-21 Verfahren zur Feststellung des Zustandes eines Quellenbereich-Fluxdetektors
DE8484309018T DE3478366D1 (en) 1983-12-30 1984-12-21 Method for determining the operability of a source range detector
ES539064A ES8702058A1 (es) 1983-12-30 1984-12-26 Un metodo de determinacion de la operabilidad de un detector del margen de la fuente situado junto a un reactor nuclear
JP59275030A JPS60158390A (ja) 1983-12-30 1984-12-28 中性子源領域検出器の動作可能性を決定する方法
KR1019840008595A KR850004696A (ko) 1983-12-30 1984-12-31 소스범위 측정기의 작동성을 결정하는 방법

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US06/567,447 US4655994A (en) 1983-12-30 1983-12-30 Method for determining the operability of a source range detector

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US4655994A true US4655994A (en) 1987-04-07

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US (1) US4655994A (de)
EP (1) EP0147212B1 (de)
JP (1) JPS60158390A (de)
KR (1) KR850004696A (de)
DE (1) DE3478366D1 (de)
ES (1) ES8702058A1 (de)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5249207A (en) * 1991-07-18 1993-09-28 Commissariat A L'energie Atomique Apparatus for monitoring the neutron flux of a nuclear reactor
US5295166A (en) * 1992-03-30 1994-03-15 Kabushiki Kaisha Toshiba Start-up range neutron monitor system
US6181759B1 (en) 1999-07-23 2001-01-30 Westinghouse Electric Company Llc Method and apparatus for determining nearness to criticality of a nuclear fueled electric power generating unit
US20050135534A1 (en) * 2003-11-07 2005-06-23 Jones James L. Nuclear material detection apparatus and method
US11081244B2 (en) * 2015-09-08 2021-08-03 Mitsubishi Electric Corporation Incore nuclear instrumentation system

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3296440A (en) * 1964-06-24 1967-01-03 Mortimer A Schultz Shutdown reactivity meter for measuring the subcritical reactivity in a nuclear reactor
US3873840A (en) * 1973-11-09 1975-03-25 Us Navy Gamma compensated pulsed ionization chamber wide range neutron/reactor power measurement system
FR2287751A1 (fr) * 1974-10-09 1976-05-07 Hartmann & Braun Ag Canal de securite dynamique pour reacteurs nucleaires
US3979256A (en) * 1975-03-04 1976-09-07 The United States Of America As Represented By The United States Energy Research And Development Administration Monitoring circuit for reactor safety systems
US4044301A (en) * 1974-04-19 1977-08-23 Commissariat A L'energie Atomique Modular ionization chamber of the boron-coating type
US4186048A (en) * 1976-09-07 1980-01-29 General Atomic Company Neutron flux monitoring system
US4493811A (en) * 1982-07-26 1985-01-15 Tokyo Shibaura Denki Kabushiki Kaisha Preamplifier for a wide range neutron flux monitoring system
US4495144A (en) * 1981-07-06 1985-01-22 Gamma-Metrics Fission chamber detector system for monitoring neutron flux in a nuclear reactor over an extra wide range, with high sensitivity in a hostile environment

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3296440A (en) * 1964-06-24 1967-01-03 Mortimer A Schultz Shutdown reactivity meter for measuring the subcritical reactivity in a nuclear reactor
US3873840A (en) * 1973-11-09 1975-03-25 Us Navy Gamma compensated pulsed ionization chamber wide range neutron/reactor power measurement system
US4044301A (en) * 1974-04-19 1977-08-23 Commissariat A L'energie Atomique Modular ionization chamber of the boron-coating type
FR2287751A1 (fr) * 1974-10-09 1976-05-07 Hartmann & Braun Ag Canal de securite dynamique pour reacteurs nucleaires
US3979256A (en) * 1975-03-04 1976-09-07 The United States Of America As Represented By The United States Energy Research And Development Administration Monitoring circuit for reactor safety systems
US4186048A (en) * 1976-09-07 1980-01-29 General Atomic Company Neutron flux monitoring system
US4495144A (en) * 1981-07-06 1985-01-22 Gamma-Metrics Fission chamber detector system for monitoring neutron flux in a nuclear reactor over an extra wide range, with high sensitivity in a hostile environment
US4493811A (en) * 1982-07-26 1985-01-15 Tokyo Shibaura Denki Kabushiki Kaisha Preamplifier for a wide range neutron flux monitoring system

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5249207A (en) * 1991-07-18 1993-09-28 Commissariat A L'energie Atomique Apparatus for monitoring the neutron flux of a nuclear reactor
US5295166A (en) * 1992-03-30 1994-03-15 Kabushiki Kaisha Toshiba Start-up range neutron monitor system
US6181759B1 (en) 1999-07-23 2001-01-30 Westinghouse Electric Company Llc Method and apparatus for determining nearness to criticality of a nuclear fueled electric power generating unit
US20050135534A1 (en) * 2003-11-07 2005-06-23 Jones James L. Nuclear material detection apparatus and method
US7142625B2 (en) * 2003-11-07 2006-11-28 Jones James L Nuclear material detection apparatus and method
US20070274426A1 (en) * 2003-11-07 2007-11-29 Jones James L Nuclear material detection method
US11081244B2 (en) * 2015-09-08 2021-08-03 Mitsubishi Electric Corporation Incore nuclear instrumentation system

Also Published As

Publication number Publication date
JPS60158390A (ja) 1985-08-19
EP0147212B1 (de) 1989-05-24
ES8702058A1 (es) 1986-12-01
ES539064A0 (es) 1986-12-01
EP0147212A3 (en) 1986-09-10
JPH0310917B2 (de) 1991-02-14
DE3478366D1 (en) 1989-06-29
EP0147212A2 (de) 1985-07-03
KR850004696A (ko) 1985-07-25

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